ML082681591
| ML082681591 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  (DPR-042, DPR-060, SNM-2506) |
| Issue date: | 09/22/2008 |
| From: | Thomas Wengert Plant Licensing Branch III |
| To: | Wadley M Northern States Power Co |
| Wengert, Thomas NRR/DORL 415-4037 | |
| Shared Package | |
| ML082590622 | List: |
| References | |
| TAC L24245, TAC MD9622, TAC MD9623 | |
| Download: ML082681591 (6) | |
Text
NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION (10-2000) 10 CFR 72 1
OF 4
PAGES LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Part 72, and, in reliance on statements and representationsheretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fueland other radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and at
..the place(s) designated below; and to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified herein.
Licensee
- 1.
Northern States Power Company, a
- 3.
License No.
SNM-2506 Minnesota corporation (NSPM) 1 Amendment No.
6
- 2.
414 Nicollet Mail l Q
Minneapolis, Minnesota, 55401-1927,",*ý 6
- 4.
- Expiration Date 4"'Otober 31,2013
- 5.
Docket or N 72"-10
.~Reference -No.
721"
- 6.
Byproduct, Source, and/or'20 7".'.- emical or Physical M8.
Ma.xlm1um Amount That Special Nuclear Material-j'f "GA
-Licensee May-.
ssess at Any One
~ Und~ffhs License A. Spent fuel:assemblies from Prairie Island Nuclear Station"*
Units 1 and 2 reactors, using.
natural water for cooling and enriched not greater than 3.85V percent U-235, and associated radioactive materials related to receipt, storage and transfer of the fuel assemblies.
B. Irradiated fuel assembly inserts from the Prairie Island Nuclear Station Units 1 and 2 reactor.
An insert may be a burnable poison rod assembly (BPRA) or a thimble plug device (TPD).
2.U a it
'Ap115.294-bU of spent fuel
"-lreo. u
.z assemnlies B
SS 304 structure, Inconel 718 spring, and borated pyrex glass.
B.
One BPRA or TPD per'spent fuel
-assembly.
Northern States Power Company was incorporated in Minnesota as a wholly owned subsidiary of Xcel Energy Inc., effective August 18, 2000. This license, as amended, was amended to reflect the Commission's consent per 10 CFR Part 72, Section 72.50, to the license transfer approved by order dated May 12, 2000.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION.,
PAGE 2
-ýOF
.4 PAGES (10-2000)
License No. SNM-2506 Amendment No. 6 10 CFR 72 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET
- 9.
Authorized Use:: For use in accordance with statements, representations, and the conditions of the Technical Specifications and Safety Analysis Report dated August 31, 1990, and supplements'dated October 29, 1990; April 2, June 5, October 9 and 31, November 15, December 11, 20, and 23, 1 991; January 17, February 6, 10, and 12, March 2 and 5, April 3, 22, and 23, July 10, August 12, 13, and 14, 1992; October 2, 1995; August 31., October 29 and November 24, 1999; and February 2, March 14 and October 16, 2000; February 12, 2001; April 16 and August 8, 2008.
The material identified in 6 and 7 above is authorized for receipt, possession, storage, and transfer.
- 10.
Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the Prairie Island ISFSI located on the Prairie Island Nuclear Generating Plant site in.Goodhue County, Minnesota.
- 11.
This site is described in Chapter 2 of the Technical Specifications. and Safety Analysis Report (TS/SAR) for the Prairie -Island ISFSI.
- 12.
The Technical Specifications containe dain Appendix A attached hereto are incorporated into the license.
NSPM shall operate the installd'irh in accordance with the Tech i/a-Specifications -in Appendix A.
- 1. NSPM shall fullyt the~
pyia scrty ur
- 13.
NSPM shall fully implemeýNtand maintain in effect all provisions of th ISFSI physical security, guard training and qualification, and-safeguards contingency plans previously aoproved by the Commission and all amendments mae pursuant the authority of 10 CF
-plans, whih c~ntin safeguaMIS inforýSl!M*.ndr1 C
1 which contain safe inf petected under 10 CF 1, are entitled: "Prairie Island Nuclear Generating Plant lndependirnt VSpent EubfuSterage -j Qtation Physical Security'Plan,"
'Revision 0, submittedIby letter dat&A__ach 10, 1,992,; PA
-ai~if*ind Nuclear,?G-enerating Plant
- Independent Spent -Fuel Storage Instdiation Seburityvc*.Frer I Idee Spet F`u g ain, ing and Qualification Plan," Revision 0, submitted by letter d&ait-d Marclf*
1h I
."**.*rl S-
ýe_
su e bd ePrairie.sla clea" Generating Plant Independent Spent, Fuel Storage InsItallatiei Sg s
Re*isi*n 0, moIrnitted by letter dated March 10, 1992.
The Technical nM I
contained in Appendix A attached *hereto are incorporated into the license Specifications required pursuaNt to 10 CFR 72.44(d), stating limits on the release of radioactive materials for compliance with~ii6Ats of 10 CFR Part 20 and ".as low~s is reasonably achievable objective" for effluents are not applicable. TN-40 cask external suf ace contamination within the limits of
- .*'X1-*
A A.
Technical Specification 3.4.1 ensures tlhatIee offsite dose willbe inconsequential. In addition, there are no normal or off-normal releases or effluenfrexpected from the double-sealed storage casks of the ISFSI.
Specifications required pursuant to. 10 CFR 72.44(d)(1), for operating procedures, for control of effluents, and for the maintenance and use of equipment in radioactive waste treatment systems, to meet the requirements of 10 CFR.72.104 are not applicable. There are, by the design of the sealed storage casks at the ISFSI, no effluent releases. Also, cask loading and unloading operations and waste treatment will occur at the Prairie Island Nuclear Generating Plant, under the specifications of its operating licenses.
- 15.
No spent nuclear fuel shall be allowed to be loaded until such time as the following preoperational license conditions are satisfied:
A A training exercise (Dry Run) of all TN-40 cask loading and handling activities shall be held, which shall include, but not be limited to, those listed, and which need not be performed in the order listed:
. U. S. NUCLEAR REGULATORY COMMISSION
- PAGE, 3
OF 4
PAGES (10-2000)
License No: SNM-2506 Amendment No. 6 10 CFR 72 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET
- a.
'Moving cask in and out of spent fuel pool area
- b.
Loading fuel assembly (using dummy assembly)
- c.
Cask drying, sealing, and cover gas backfilling operations
- d.
Moving cask to, and placing it on, the storage pad
- e.
Returning the cask to the auxiliary building
- f.
Unloading the cask
- g.
Decontaminating the cask
- h.
All dry-run activities'ghall`b done usingwritt~enhprocedures i
The activitie above shall be performed or mdifi*ed ai that each,activity can be successfully executed beforeactu*
The Prairie Island-Nuc0iar-Generating Plant Emergency Pan:ha*
-as required, to lude the-,lS*.SI C
A training movie shall be, pped for rair NuclearG
- Program, estdiblishing an lf&E*SITraining'and Certificatori
-rogram th following:
nd performed to show al fuel loading.
reviewed and modified, a.
- b.
-ISF Srac
- c.
ISFSI SafE
- d.
Fuel loadir
'enerating Plant Training ijill include the
- e.
ISFSI License (ovei D
The Prairie Island Nuclear Generating Plant Radiation Protection Procedures shall be reviewed and modified, as required, to include the ISFSI.
E The Prairie Island Nuclear Generating Plant Administrative Procedures shall be reviewed and modified, as required, to include the ISFSI.
F A procedure shall be developed and implemented for the documentation of the characterizations performed to Select spent fuel to be stored in the casks. Such procedure shall include independent verification of fuel assembly selection by an individual other than the original individual making the selection.
G A procedure shall be developed and implemented for two independent determinations (two samples analyzed by different individuals) of the boron concentration in the water used to fill the cask cavity for fuel loading and unloading activities.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION.
PAGE 4
OF 4
PAGES (I0-200o)
License No. SNM-2506 Amendment No. 6 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET H
Written procedures shall be implemented to describe actions to be taken during operation, off-normal, and emergency conditions.
1 6.
The design, construction, and operation of the ISFSI shall be accomplished in accordance with the U.S.
Nuclear Regulatory Commission Regulations specified in Title 10 of the U.S. Code of Federal Regqulations. All commitments to the applicable NRC regulatory guides and to engineering and construction codes shall be carried out.
- 17.
Fuel and cask movement and handling activities that are to be performed in the Prairie Island Nuclear Generating Plant Auxiliary Building will be governed by the requirements of the Prairie Island Nuclear Generating Plant Facility Operating Licenses (DRP-42 and -60) and associated Technical Specifications.
- 18.
This license is effective as of the date of issuance shown below.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Eriic J. enner, Chief Licensing Branch Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance: October 19, 1993 As amended by Amendment 6 dated September 22, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 6 TO MATERIALS LICENSE NO. SNM-2506 DOCKET NO. 72-10 Replace the following page of Appendix A, "Technical Specifications," with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT 6-1 6-1
6.0 ADMINISTRATIVE CONTROLS 6.1 GENERAL The Prairie Island ISFSI is located on the Prairie Island Nuclear Generating Plant site and will be managed and operated by Northern States Power Company, ' Minnesota corporation (NSPM) staff. The administrative controls shall be in accordance with the requirements of the Prairie Island Nuclear Generating Plant Facility Operating'Licenses (DPR-42 and -60) and associated Technical Specifications, as appropriate.
6.2 ENVIRONMENTAL MONITORING PROGRAM The licensee shall include the Prairie Island ISFSI in the environmental monitoring program for the Prairie Island Nuclear Generating Plant.. An environmental monitoring program is required pursuant to 10 CFR 72.44(d)(2). The licensee shall include the ISFSI in the environmental monitoring report for the Prairie Island Nuclear Generating Plant, and a copy shall be sent to the Director, Office of Nuclear Material Safety and Safeguards.
6.3 ANNUAL ENVIRONMENTAL REPORT An annual report, as required by 10 CFR 72.44(d)(3), shall be submitted to the NRC Region Ill, Office, with a copy to the Director, Office of Nuclear Material Safety and Safeguards, within 60 days after January 1 of each year. This report should specify the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous year of operation and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent release.
6-1 Amendment 4 dated September 22, 2008